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Department Of Reactor Safety Research Japan Atomic Energy Researth Institute | 論文
- Evaluation of High Temperature Tensile and Creep Properties of Light Water Reactor Coolant Piping Materials for Severe Accident Analyses
- Effect of Microstructure on Failure Behavior of Light Water Reactor Coolant Piping under Severe Accident Conditions
- Vapor Condensation and Thermophoretic Aerosol Deposition of Cesium Iodide in Horizontal Thermal Gradient Pipes
- Enhancement of CsI Aerosol Size in Superheated Steam in Reactor Piping under Severe Accidents
- Experimental and Analytical Study on the Behavior of Cesium Iodide Aerosol/Vapor Deposition onto Inner Surface of Pipe Wall under Sever Accident Conditions
- Radionuclide Release from Mixed-Oxide Fuel under High Temperature at Elevated Pressure and Influence on Source Terms
- Proposal of Simplified Model of Radionuclide Release from Fuel under Severe Accident Conditions Considering Pressure Effect
- Intramembrane Signaling Mediated by Hydrogen-Bonding of Water and Carboxyl Groups in Bacteriohodopsin and Rodopsin^1
- SCDAP/RELAP5 Analysis of Station Blackout with Pump Seal LOCA in Surry Plant
- Decrease of Cesium Release from Irradiated UO_2 Fuel in Helium Atmosphere under Elevated Pressure of 1.0 MPa at Temperature up to 2,773K
- Enhancement of Cesium Release from Irradiated Fuel at Temperature above 2,800 K
- Influence of Pressure on Cesium Release from Irradiated Fuel at Temperatures up to 2,773K
- Natural Convection Heat Transfer in the Horizontal Dry Storage System for the LWR Spent Fuel Assemblies
- Irradiation Behavior of Large Grain UO_2 Fuel Rod by Active Powder